Actions for Source term experiment STEP-3 simulating a PWR severe station blackout [electronic resource].

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Source term experiment STEP-3 simulating a PWR severe station blackout [electronic resource].

Published
Argonne, Ill. : Argonne National Laboratory, 1987.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 5 : digital, PDF file
Additional Creators
Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
For a severe PWR accident that leads to a loss of feedwater to the steam generators, such as might occur in a station blackout, fission product decay heating will cause a water boiloff. Without effective cooling of the core, steam will begin to oxidize the Zircaloy cladding. The noble gases and volatile fission products, such as Cs and I, that are major contributors to the radiological source term, will be released from the damaged fuel shortly after cladding failure. The accident environment when these volatile fission products escape was simulated in STEP-3 using four fuel elements from the Belgonucleaire BR3 reactor. The primary objective was to examine the releases in samples collected as close to the test zone as possible. In this paper, an analysis of the temperatures and hydrogen generation is compared with the measurements. The analysis is needed to estimate releases and characterize conditions at the source for studies of fission product transport.
Report Numbers
E 1.99:conf-871101-12
conf-871101-12
Subject(s)
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Note
Published through SciTech Connect.
05/21/1987.
"conf-871101-12"
"DE87011376"
California State Air Resources Board, Los Angeles, CA, USA, 15 Nov 1987.
Baker, L. Jr.; Simms, R.; Ritzman, R.L.
Funding Information
W-31109-ENG-38
View MARC record | catkey: 14370325